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CSNI0076 BETHSY/6.9C.

BETHSY/6.9C, Loss of residual heat removal system during mid-loop operation

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1. NAME OF EXPERIMENT:  BETHSY/6.9C.
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2. COMPUTERS
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Program name Package id Status Status date
BETHSY/6.9C CSNI0076/01 Report 01-JUN-1998

Machines used:

Package ID Orig. computer Test computer
CSNI0076/01 Many Computers
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3. DESCRIPTION OF TEST FACILITY

The BETHSY integral test facility located in the Nuclear Research Center in Grenoble (France) is a scaled down model of a 3 loop 900 eMW FRAMATOME PWR; the overall scaling factor applied to every volume, mass flowrate and power level is close to 1/100, while elevations are 1/1 in order to preserve the gravitational heads.
  
BETHSY facility is a 3-loop replica of a 900 MWe FRAMATOME PWR
- 428 heater rod core simulation, electrically heated
- 3 secondary steam generators equipped with 34 U-tubes of original dimensions
- primary system pressure up to 17.2 MPa, secondary side pressure up to 8 MPa
- initial power level of test section allows for 10 % of scaled nominal full power
- heat losses controlled by external heater system
- HPIS and LPIS available
  
Scaling Information:
- power and volume scaling 1/100 corresponding to FRAMATOME BWR of the 900 MWe class
- full length core simulator, decay power level and nominal flow rates scaled 1/100
- geodetical elevations of all components preserved 1/1 to simulate gravitational head
- loop piping diameter of hot legs dimensioned to preserve FROUDE number criterion of full size plant
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4. DESCRIPTION OF TEST

The aim of this test performed in 1992 was to study the accident transient following a failure of the residual heat removal system with the pressurizer and SGI outlet plenum manways open. There was no non condensable gas in the test.
The objectives were:
Simulation of integral plant behaviour under atmospheric conditions (open system) with anticipated loss of Residual Heat Removal System during mid-loop operation
- study physical phenomena under very low system pressure, in particular the behaviour of pressurizer and surge line
- core uncovery and reflooding
- effects of loss of primary coolant and refilling by RHRS
- 'open' calculations requested to allow assessment of code applicability for conditions not anticipated during development of codes (extreme low pressure)
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6. PHENOMENA TESTED

Analyze reactor system response to a loss of the Residual Heat Removal System during Mid-loop operation. The overall aims of the exercise are:
- to show the status of model development and computer codes in addressing low power (0.5%), low pressure (1 bar) transients,
- compare different computer models, and
- increase the common understanding of transients at mid-loop (shutdown) operating conditions.
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9. STATUS
Package ID Status date Status
CSNI0076/01 01-JUN-1998 Report Only
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10. REFERENCES
CSNI0076/01, included references:
- G. Kimber, C. Leveque and G. Lavialle:
ISP-38 on BETHSY Test 6.9C
Final Report NEA/CSNI/R(97)38 Vol. 1 and 2 (June 1998)
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11. TEST DESIGNATION:  6.9c.
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12. PROGRAMMING LANGUAGE(S) USED
No specified programming language
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15. ESTABLISHMENT

CEA Grenoble, France
AEA Technology plc, UK
Tractebel SA, Belgium
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16. MATERIAL AVAILABLE
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17. CATEGORIES
  • Y. Integral Experiments Data, Databases, Benchmarks

Keywords: data, loss-of-coolant accident, transients.